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Title: Performance assessment of KORAT-3D on the ANL IBM-SP computer

Abstract

The TENAR code is currently being developed at the Russian Federal Nuclear Center (VNIIEF) as a coupled dynamics code for the simulation of transients in VVER and RBMK systems and other nuclear systems. The neutronic module in this code system is KORAT-3D. This module is also one of the most computationally intensive components of the code system. A parallel version of KORAT-3D has been implemented to achieve the goal of obtaining transient solutions in reasonable computational time, particularly for RBMK calculations that involve the application of >100,000 nodes. An evaluation of the KORAT-3D code performance was recently undertaken on the Argonne National Laboratory (ANL) IBM ScalablePower (SP) parallel computer located in the Mathematics and Computer Science Division of ANL. At the time of the study, the ANL IBM-SP computer had 80 processors. This study was conducted under the auspices of a technical staff exchange program sponsored by the International Nuclear Safety Center (INSC).

Authors:
; ;  [1];  [2]
  1. Russian Federal Nuclear Center (Russian Federation)
  2. Argonne National Lab., IL (United States)
Publication Date:
OSTI Identifier:
678158
Report Number(s):
CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009143
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999
Country of Publication:
United States
Language:
English
Subject:
99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LWGR TYPE REACTORS; WWER TYPE REACTORS; REACTOR ACCIDENTS; TRANSIENTS; K CODES; NEUTRON TRANSPORT; T CODES; PERFORMANCE; PARALLEL PROCESSING; IBM COMPUTERS; REACTOR KINETICS

Citation Formats

Alexeyev, A.V., Zvenigorodskaya, O.A., Shagaliev, R.M., and Taiwo, T.A. Performance assessment of KORAT-3D on the ANL IBM-SP computer. United States: N. p., 1999. Web.
Alexeyev, A.V., Zvenigorodskaya, O.A., Shagaliev, R.M., & Taiwo, T.A. Performance assessment of KORAT-3D on the ANL IBM-SP computer. United States.
Alexeyev, A.V., Zvenigorodskaya, O.A., Shagaliev, R.M., and Taiwo, T.A. Wed . "Performance assessment of KORAT-3D on the ANL IBM-SP computer". United States.
@article{osti_678158,
title = {Performance assessment of KORAT-3D on the ANL IBM-SP computer},
author = {Alexeyev, A.V. and Zvenigorodskaya, O.A. and Shagaliev, R.M. and Taiwo, T.A.},
abstractNote = {The TENAR code is currently being developed at the Russian Federal Nuclear Center (VNIIEF) as a coupled dynamics code for the simulation of transients in VVER and RBMK systems and other nuclear systems. The neutronic module in this code system is KORAT-3D. This module is also one of the most computationally intensive components of the code system. A parallel version of KORAT-3D has been implemented to achieve the goal of obtaining transient solutions in reasonable computational time, particularly for RBMK calculations that involve the application of >100,000 nodes. An evaluation of the KORAT-3D code performance was recently undertaken on the Argonne National Laboratory (ANL) IBM ScalablePower (SP) parallel computer located in the Mathematics and Computer Science Division of ANL. At the time of the study, the ANL IBM-SP computer had 80 processors. This study was conducted under the auspices of a technical staff exchange program sponsored by the International Nuclear Safety Center (INSC).},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 80,
place = {United States},
year = {1999},
month = {9}
}